참고문헌
- S.A. El-mongy, Overview of Research Reactors (RR) Worldwide and Their Applications, 2018.
- Saclay CEA, OSIRIS Nuclear Reactors and Services Department, 2008.
- C. Gonnier, J. Estrade, G. Bignan, et al., Experimental devices in Jules Horowitz reactor and first orientations for the experimental programs, in: Proceedings of IGORR 18th Meeting, Sydney, Australia, December, 2017.
- C.J. Stanley, F.M. Marshall, Advanced test reactore A national scientific user facility, in: Proceedings of ICONE 16th Conference, Orlando, Florida, USA, May 11-15, 2008, https://doi.org/10.1115/icone16-48426.
- N. Xoubi, Jordan Research and Training Reactor (JRTR) Utilization Facilities, 2010. IAEA-TM-38728.
- E. Privas, C. Bouret, S. Nicolas, et al., Monte-carlo coupled depletion codes efficiency for research reactor design, in: Proceedings of IGORR 18th Meeting, Sydney, Australia, December, 2017.
- A. Peron, F. Malouch, C.M. Diop, Improvement of nuclear heating evaluation inside the core of the OSIRIS material testing reactor, in: Proceedings of EPJ Web of Conferences, vol. 106, 2016, https://doi.org/10.1051/epjconf/201610605006, 05006.
- D. Parrat, G. Bignan, B. Maugard, et al., The future Jules Horowitz material testing reactor: an opportunity for developing international collaborations on a major European irradiation infrastructure, in: Proceedings of International Conference on WWER Fuel Performance, Modelling and Experimental Support, Vama, Bulgaria, September 26- October 3, 2015.
- F. Jeury, J. Politello, C. D'Aletto, et al., HORUS3D/N neutron calculation tool, a deterministic scheme dedicated to JHR design and safety studies, Nucl. Sci. Eng. 189 (2018) 188-198, https://doi.org/10.1080/00295639.2017.1381505.
- W. Haeck, B. Cochet, L. Aguiar, Monte Carlo depletion calculations using VESTA 2.1 new features and perspectives, in: Proceedings of PHYSOR Conference, Knoxville, Tennessee, USA, April 15-20, 2012.
- D.B. Pelowitz, J.T. Goorley, M.R. James, et al., MCNP6 USER'S MANUAL Version 1.0, LA-CP-13-00634, Rev. 0, 2013.
- H. Lee, W. Kim, P. Zhang, et al., MCS - a Monte Carlo particle transport code for large-scale power reactor analysis, Ann. Nucl. Energy (2019). https://doi.org/10.1016/j.anucene.2019.107276.
- J. Yu, H. Lee, M. Lemaire, et al., MCS based neutronics/thermal-hydraulics/fuelperformance coupling with CTF and FRAPCON, Comput. Phys. Commun. 238 (2019) 1-18, https://doi.org/10.1016/j.cpc.2019.01.001.
- M.K. Jaradat, V. Radulovic, C.J. Park, et al., Verification of MCNP6 model of the Jordan Research and Training Reactor (JRTR) for calculations of neutronic parameters, Ann. Nucl. Energy 96 (2016) 96-103, https://doi.org/10.1016/j.anucene.2016.06.003.
- K.O. Kim, B.J. Jun, B. Lee, et al., Neutronics experiment results in commissioning stage B of JRTR, in: Proceedings of RRFM Conference, Munich, Germany, March 11-15, 2018.
- J. Jang, W. Kim, S. Jeong, et al., Validation of UNIST Monte Carlo code MCS for criticality safety analysis of PWR spent fuel pool and storage cask, Ann. Nucl. Energy 114 (2018) 495-509, https://doi.org/10.1016/j.anucene.2017.12.054.
- J. Yu, H. Lee, H. Kim, et al., Preliminary coupling of the Thermal/Hydraulic solvers in the Monte Carlo code MCS for practical LWR analysis, Ann. Nucl. Energy 118 (2018) 317-335, https://doi.org/10.1016/j.anucene.2018.03.043.
- H. Lee, C. Kong, D. Lee, Status of Monte Carlo code development at UNIST, in: Proceedings of PHYSOR Conference, the Westin Miyako, Kyoto, Japan, September 28-October 3, 2014 ([USB]).
- T.D.C. Nguyen, H. Lee, S. Choi, et al., Validation of UNIST Monte Carlo code MCS using VERA progression problems, Nucl. Eng. Tech. (2019), https://doi.org/10.1016/j.net.2019.10.023.
- B. Ebiwonjumi, H. Lee, J. Choe, et al., MCS analysis of Westinghouse 3-loop PWR multi-cycle operation, in: Proceedings of KNS Autumn Meeting, Yeosu, Korea, October 25-26, 2018 ([USB]).
- V. Dos, H. Lee, J. Choe, et al., Validation of Monte Carlo MCS code for OPR -1000 operation, in: Proceedings of NURER Conference, Ramada Plaza Jeju, Korea, September 30- October 3, 2018 ([USB]).
- H. Lee, E. Jeong, H. Lee, et al., Verification of MCS VHTR modeling capability, in: Proceedings of RPHA17 Conference, Chengdu, China, August 24-25, 2017 ([USB]).
- T.D.C. Nguyen, H. Lee, et al., LPPT analysis of APR1400 reactor core by UNIST Monte Carlo code MCS, in: Proceedings of RPHA17 Conference, Chengdu, China, August 24-25, 2017 ([USB]).
- T.D.C. Nguyen, J. Choe, B. Ebiwonjumi, et al., Core design of long-cycle small modular lead-cooled fast reactor, Int. J. Energy Res. 43 (2019) 254-273, https://doi.org/10.1002/er.4258.
- P. Zhang, H. Lee, D. Lee, On the transfer matrix of the modified power method, Comput. Phys. Commun. 222 (2018) 102-112, https://doi.org/10.1016/j.cpc.2017.09.022.
- H. Lee, S. Choi, D. Lee, A hybrid Monte Carlo/Method-of-Characteristics method for efficient neutron transport analysis, Nucl. Sci. Eng. 180 (2015) 69-85, https://doi.org/10.13182/NSE13-102.
- P.K. Romano, B. Forget, Parallel fission bank algorithms in Monte Carlo criticality calculations, Nucl. Sci. Eng. 170 (2017) 125-135, https://doi.org/10.13182/NSE10-98.
- M. Pusa, J. Leppanen, Computing the matrix exponential in burnup calculations, Nucl. Sci. Eng. 164 (2017) 140-150, https://doi.org/10.13182/NSE09-14.
- A.E. Isotalo, P.A. Aarnio, Comparison of depletion algorithms for large systems of nuclides, Ann. Nucl. Energy 38 (2011) 261-268, https://doi.org/10.1016/j.anucene.2010.10.019.
- J. Park, A. Khassenov, W. Kim, et al., Comparative analysis of VERA depletion benchmark through consistent code-to-code comparison, Ann. Nucl. Energy 124 (2019) 385-398, https://doi.org/10.1016/j.anucene.2018.10.024.
- W. Kim, H. Lee, S. Choi, et al., Hybrid depletion method for the light water reactor analysis wonkyeong, in: Proceeding of M&C 2017 Conference, Jeju, Korea, April 16-20, 2017 ([USB]).
- H. Lee, Development of a New Monte Carlo Code for High-Fidelity Power Reactor Analysis Thesis (Doctoral), Ulsan National Institute of Science and Technology, 2019 ([USB]).
- B.T. Mervin, Monte Carlo and Depletion Reactor Analysis for High-Performance Computing Applications, Doctoral Dissertation University of Tennessee - Knoxville, 2013. https://trace.tennessee.edu/utk_graddiss/2601.
- V. Dos, H. Lee, Y. Jo, et al., Verification of MCS Monte Carlo code for the JRTR research reactor, in: Proceedings of the PHYSOR Conference, Cancun: American Nuclear Society, Apr 22-26, 2018 ([USB]).
- K.O. Kim, B.J. Jun, B. Lee, et al., Comparison of first criticality prediction and experiment of the Jordan research and training reactor (JRTR), Nucl. Eng. Tech. (2019) 6-10, https://doi.org/10.1016/j.net.2019.06.027.
- I.F. Farouki, Full-core burn-up calculations using MCNP6 code for the Jordan research and training reactor, in: Proceeding of Research Reactor Fuel Management Conference, Amman, Jordan, March, 2019.
- A.H. Fadaei, S. Setayeshi, Control rod worth calculation for VVER-1000 nuclear reactor using WIMS and CITATION codes, Prog. Nucl. Energy 51 (2009) 184-191, https://doi.org/10.1016/j.pnucene.2008.03.003.
- Y. Qiu, Z. Wang, K. Li, et al., Calculation of adjoint-weighted kinetic parameters with the reactor Monte Carlo code RMC, Prog. Nucl. Energy 101 (2017) 424-434, https://doi.org/10.1016/j.pnucene.2017.03.023.
- M.H. Rabir, M.R.M. Zin, M.D, et al., Neutron flux and power in RTP core-15, in: Proceeding of AIP Conference, vol. 1704, 2016, https://doi.org/10.1063/1.4940114,050018-1-050018-11.
- M.L. Fensin, M.R. James, J.S. Hendricks, et al., The new MCNP6 depletion capability, in: Proceedings of ICAPP Conference, Chicago, USA, June 244-28, 2012.
- I.J. Bratton, Modeling and Validation of the Fuel Depletion and Burnup of the OSU Research Reactor Using MCNPX/CINDER'90, Thesis (Master), The Ohio State University, 2012.
- J.S. Hendricks, G.W. Mckinney, M.L. Fensin, et al., MCNPX 2.6.0 Extensions, LAUR-08-2216, April 11, 2008.
- U.S. Hidayat, A. Agung, M. Lemaire, et al., MCS cycle depletion analysis and validation of excess reactivity and shutdown margin for the Kartini triga Mark II research reactor, in: Proceedings of ICAPP Conference, Juan-Les-Pins, France, May 12-15, 2019.
- K.N. Choo, M.S. Cho, S.W. Yang, et al., Contribution of Hanaro irradiation technologies to national nuclear R&D, Nucl. Eng. Technol. 46 (2014) 501-512, https://doi.org/10.5516/NET.07.2014.006.
피인용 문헌
- Analysis of VVER-1000 mock-up criticality experiments with nuclear data library ENDF/B-VIII.0 and Monte Carlo code MCS vol.53, pp.1, 2020, https://doi.org/10.1016/j.net.2020.06.015